Fission gas bubbles and recrystallization-induced degradation of the effective thermal conductivity in U-7Mo fuels-Reference-Cited by-同舟云学术

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Fission gas bubbles and recrystallization-induced degradation of the effective thermal conductivity in U-7Mo fuels

Published:2018-12 Issue: Volume:511 Page:438-445
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Liang Linyun,Kim Yeon Soo,Mei Zhi-Gang,Aagesen Larry K.^ORCID,Yacout Abdellatif M.

Funder

U.S. Department of Energy

National Nuclear Security Administration

Office of Material Management and Minimization (NA-23) Reactor Conversion Program

U.S. Department of Energy, Office of Science

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference42 articles.

1. Fission induced swelling and creep of U–Mo alloy fuel

2. Heat capacity measurements of U0.80Zr0.20 and U0.80Mo0.20 alloys from room temperature to 1300 K

3. Thermo-physical properties of DU–10wt.% Mo alloys

4. Thermophysical Properties of U–Mo/Al Alloy Dispersion Fuel Meats

Cited by 21 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Thermal conductivity of U-Mo alloy fuel;Journal of Nuclear Materials;2024-12

2. Calculation of the effective thermal conductivity of porous polycrystalline U-10Mo alloy based on phase-field simulation;Nuclear Engineering and Design;2023-11

3. The reconciliation and validation of a combined interatomic potential for the description of Xe in γU-Mo;Frontiers in Nuclear Engineering;2023-07-19

4. Kinetics of substitutional Xe and self-interstitial Mo in γ U–10Mo: a molecular dynamic study;Radiation Effects and Defects in Solids;2023-06-19

5. An experimentally validated mesoscale model for the effective thermal conductivity of U-Zr fuels;Journal of Nuclear Materials;2023-02

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